Similar Documents at Hatch |
|---|
|
LER-1981-078, /03L-0:on 810820,reactor Core Isolation Cooling Flow Controller Demand Was at Less than 100% While in Either Auto or Manual.Caused by Faulty Resistor in Ramp Generator. Units Replaced |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3661981078R03 - NRC Website |
|
text
e U.S. NUCLEAR REGULATORY COMMISSION NRC FORM 366 LICENSEE EVENT REPORT
'o CONTROL BLOCK: l l
l l
l l Jh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
lo l1l l Gl Al El Il HI 2l@l 01 Ol -l 0101010101 - 10 l 01@l 4 lI ll llll l@l l
l@
7 3 9 LICENSEE CODE 14 15 LICENSE NOUdEH 25 26 LICENSE TYPE JO 57 CAT t8 COffT 1011]
SE l Ll@l 0l 5l 0l 0l 0l 3l 6l 61@l 018 l 210 l 8 l11@l 0 l 9 l 1101811 l@
7 8
60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT OATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h I O 12 I I On 8-20-81. with Unit 2 at steadv state 88.3*L thermn1 nntaor - tah i l o t-h o I
10 l a l l "ECCS Status Check" was being performed and on 8-21-81 with Unit 2 at I
/
1014i i steady state 86.9% thermal power, an operator noticed that the'RCIC flowl Icontroller demand was at 4 100% while in either auto or in manual.
RCICI O s
!O is l lwas declared inop and per Tech Spec 3.7.3,HPCI was operable.
There werel 1017 l [ no effects upon public health and safety due to this event.
This is a I
IOisiirepetitive occurrence (Ref. LER 50-366/1981-010).
1 DE CODE SB E
COMPONENT CODE SU8C NE SU E
10l91 l Cl El@ LE_j@ [E_J@ II lN lS !T lR lU lh W@ [Zj @
i 8
9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER EVENT YEAR REPORT NO.
CODE TYPE NO.
@ sgg/RO 1811]
l-- l 1017 l 81 LJ 10 13 l I
l-l LO_1 M
a
_ 21 22 23 24 26 27 N
N 30 31 32 K f ACT C ON PLANT 4E HOURS 22 S8 i FO 1 8.
SUPPL M$t ACTURER lC]@ W @
W@
lZl@
10 l010 l0 l lYl@
lY l@
(N_j@
lG10l8lOl@
33 34 35 3/
40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h g lThe cause was due to ai fa61ty resistor in the RCIC ramp generator.
Thisi
,, jii icaused self sync control module to fail on 8-20-81, and the ramn eenera-1 i,i,,i tor to fail on 8-21-81.
Thefunite were replaced on those respective I
i,,.,ijdates and RCIC was proven operable both times.
The unit is now in full I i,giicompliance with the requirements and no further reporting is required.
I 7
8 9 80 ST
% POWER OTHER STATL'S DISCOV RY DISCOVERY DEJCRIPTION IiIsI LEj@ l0l8l8l@
NA
_J L11@l ooerator observation i
ACTIVITY CO TENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELE ASE li is I Lzl @ L2J@l MA l
l M
l PERSONNEL EXPOS ES NUMBE R TYPE
DESCRIPTION
LLLJ l 0101 Ol@l ZI@l MA I
' PEnSONNd'iN>u'R'iES oESCRiPriON@
NUMeER W l01OJol@l m
I 8 3 11 12 80 LOSS OF OR OAMAGE TO FACILITY TYPE DESCRIP TION m
I LLLil LZJ@l 8109220468 810910 1
8 9 to DESCRIPTION @
PDR ADOCK NRC USE oNLY 0500036,6 l 2 l o f Lu[81 ISSUE s
po; i
m ii,,,ii,,i3 N,-
7 a o io ss 69 so g 1
m yyn,,,n,,,,ny,C. L. Coggin - Supt. Plt. Eng. Serv.
GE-En 2,
- pggy,
i
( -... '-
LER #: 366/1981-078 Licensee:
Georgia Power-Company Facility Name:
Edwin I. Hatch j-Docket #:- 50-366
Narrative
Report 3
[
for LER 50-366/1981-078 i
. On.8-20-81, with Unit 2 at steady _stete 88.3% thermal' power,;
the "ECCS Status Check" (HNP-2-1119) was being performed.
It was observed by the shift.perrannel that 'the RCIC flow controller was not indicating _ greater than :100%. demand while.
the RCIC system was. in-standby. condition.
The' controller was F
placed in manual and the 1 demand: dropped ' further.
The RCIC system was declared inoperable (Ref: Deviation-2-81-138) and per Tech Spec 3.7.3, HPCI. was operable.. No 'significant event occurred.
i, Upon investigation _it was dete'rmined that the self sync.
I control.. module. output circuit was broken.
The module was 1
i replaced and 'the system was proven operable per HNP-2-3405 "RCIC Pump Operability".
i La 8-21-81, with Unit 2 at steady state 86.9% thermal power, a control room operator observed.that the RCIC. flow controller, while RCIC vas in standby mode, drift'ed down from. greater than 100% demand to less than 70% demand.
Placing the controller in manual, the demand ~ drif ted further downward.
The RCIC i
system was declared inoperable -(Ref: Deviati~on 2-81-139) and per Tech : Spec 3.7.3, HPCI was operable.
No significant event accurred.
I Upon investigation it was discovered that-a. resistor in the RCIC ramp generator circuitry was defective and was heating' th'e circuitry to a point of failure.
As the resistor _ cooled, the ' circuitry became operable.
This defective resistor was-
+
- the cause of the self sync' module failing.on 8-20-81.-
The ramp generator we:: ' replaced, i
' This is a-repetitive event (Ref: LER 50-366/1981-10) and there l
were no effects upon public - ~ health and safety-due to this
. event.
The unit is now in full compliance with
'the requirements and no-further reporting is required.
}
~
a
%r
^^
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000366/LER-1981-001-03, /03L-0:on 810102,during Refueling,Drywell Isolation Valve 2T48/F209 Found Leaking When LLRT Performed on Drywell to Torus Dp Sys.Caused by Scratches on Valve Seat Due to Valve Closing on Debris | /03L-0:on 810102,during Refueling,Drywell Isolation Valve 2T48/F209 Found Leaking When LLRT Performed on Drywell to Torus Dp Sys.Caused by Scratches on Valve Seat Due to Valve Closing on Debris | | | 05000366/LER-1981-001, Forwards LER 81-001/03L-0.Detailed Event Analysis Encl | Forwards LER 81-001/03L-0.Detailed Event Analysis Encl | | | 05000321/LER-1981-001, Forwards LER 81-001/01T-0 | Forwards LER 81-001/01T-0 | | | 05000321/LER-1981-001-01, /01T-0:on 801228,HPCI Steam Line Pressure Switches 1E41-N001a,c,d Actuated Outside Tech Specs.Caused by Switch Setpoint Drift.Switches Recalibr | /01T-0:on 801228,HPCI Steam Line Pressure Switches 1E41-N001a,c,d Actuated Outside Tech Specs.Caused by Switch Setpoint Drift.Switches Recalibr | | | 05000366/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000366/LER-1981-002-03, /03L-0:on 810106,reactor Core Isolation Cooling Steamline Pressure Switches 2E51-NO19A & C Were Found to Actuate Below Tech Spec Limits.Caused by Setpoint Drift. Switches Recalibr | /03L-0:on 810106,reactor Core Isolation Cooling Steamline Pressure Switches 2E51-NO19A & C Were Found to Actuate Below Tech Spec Limits.Caused by Setpoint Drift. Switches Recalibr | | | 05000321/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000321/LER-1981-002-03, /03L-0:on 810101,more than 5 Gpm Leaked Into Drywell W/Reactor at 401 Mwe.Caused by Mechanical Seal Leaking Water from Reactor Recirculation pump,1B31-C001A. Seal Replaced | /03L-0:on 810101,more than 5 Gpm Leaked Into Drywell W/Reactor at 401 Mwe.Caused by Mechanical Seal Leaking Water from Reactor Recirculation pump,1B31-C001A. Seal Replaced | | | 05000366/LER-1981-003-03, /03L-0:on 810223,core Max Fraction of Limiting Power Density Found to Be Greater than Frtp During Startup. Caused by Time Delays for Adjusting Rods,Running Transient Incore Probe Scans & Processing Time for Computer | /03L-0:on 810223,core Max Fraction of Limiting Power Density Found to Be Greater than Frtp During Startup. Caused by Time Delays for Adjusting Rods,Running Transient Incore Probe Scans & Processing Time for Computer | | | 05000321/LER-1981-003-03, /03L-0:on 810130,HPCI Governor Valve Stuck Open. Caused by Lift Rod Being Bent & Galled Due to Interference Between Lift Rod Fork Connector & Valve Lever.Damaged Rod Replaced,Upper Guide Bushing Honed & Fork Modified | /03L-0:on 810130,HPCI Governor Valve Stuck Open. Caused by Lift Rod Being Bent & Galled Due to Interference Between Lift Rod Fork Connector & Valve Lever.Damaged Rod Replaced,Upper Guide Bushing Honed & Fork Modified | | | 05000366/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000321/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000366/LER-1981-004, Forwards LER 81-004/03L-0 | Forwards LER 81-004/03L-0 | | | 05000366/LER-1981-004-03, /03L-0:on 810122,nozzle Loads Found Exceeding Vendor Allowables for Reactor Core Isolation Cooling Steam Turbine During Reanalysis of Piping & Hangers Per IE Bulletin 79-14.Caused by Ae Error in Sys Design | /03L-0:on 810122,nozzle Loads Found Exceeding Vendor Allowables for Reactor Core Isolation Cooling Steam Turbine During Reanalysis of Piping & Hangers Per IE Bulletin 79-14.Caused by Ae Error in Sys Design | | | 05000321/LER-1981-004, Forwards LER 81-004/03L-0 | Forwards LER 81-004/03L-0 | | | 05000321/LER-1981-004-03, /03L-0:on 810106,w/unit in Steady State Power Operation,Qa Audit Showed That Temporary Procedure Change HNP-818 Was Not Approved by Plant Manager within 14 Days of Implementation.Caused by Deletion of Requirement | /03L-0:on 810106,w/unit in Steady State Power Operation,Qa Audit Showed That Temporary Procedure Change HNP-818 Was Not Approved by Plant Manager within 14 Days of Implementation.Caused by Deletion of Requirement | | | 05000366/LER-1981-005-01, /01T-0:on 810126,reactor Pressure Vessel Core Spray Loops Discovered Inoperable.Caused by Procedure HNP-2-1230 Being Performed,Closing Manual Injection Valves 2E21-F007A & B.Valves Reopened & Procedure Changed | /01T-0:on 810126,reactor Pressure Vessel Core Spray Loops Discovered Inoperable.Caused by Procedure HNP-2-1230 Being Performed,Closing Manual Injection Valves 2E21-F007A & B.Valves Reopened & Procedure Changed | | | 05000366/LER-1981-005, Forwards LER 81-005/01T-0 | Forwards LER 81-005/01T-0 | | | 05000321/LER-1981-005-03, /03L-0:on 810113,during Steady State Operation, Drywell Temp Recorder IT47-R612 Found to Be Inoperative. Caused by Misalignment of Cam Follower Contact W/Main Programming Cam.Follower Adjusted to Maintain Contact W/Cam | /03L-0:on 810113,during Steady State Operation, Drywell Temp Recorder IT47-R612 Found to Be Inoperative. Caused by Misalignment of Cam Follower Contact W/Main Programming Cam.Follower Adjusted to Maintain Contact W/Cam | | | 05000321/LER-1981-005, Forwards LER 81-005/03L-0 | Forwards LER 81-005/03L-0 | | | 05000366/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000366/LER-1981-006-03, /03L-0:on 810123,standby Gas Treatment Sys Filter train,2T46-D001A,removed Less Halogenated Hydrocarbon Refrigerant Gas than Required by Tech Specs During Testing by Vendor.Caused by Defective Charcoal in Filter Bed | /03L-0:on 810123,standby Gas Treatment Sys Filter train,2T46-D001A,removed Less Halogenated Hydrocarbon Refrigerant Gas than Required by Tech Specs During Testing by Vendor.Caused by Defective Charcoal in Filter Bed | | | 05000321/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000321/LER-1981-006-03, /03L-0:on 810119,standby Liquid Control Pump a Discharge Relief Valve 1C41-F029A Operated Outside Tech Spec.Caused by Setpoint Drift.Valve Reset | /03L-0:on 810119,standby Liquid Control Pump a Discharge Relief Valve 1C41-F029A Operated Outside Tech Spec.Caused by Setpoint Drift.Valve Reset | | | 05000321/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000321/LER-1981-007-03, /03L-0:on 810203 & 19,unit 1 Cable Spread Room Sprinkler Sys Was Inoperable for Period Greater than 14 Days & Special Repts Were Not Issued.Caused by Personnel Error. Personnel Reinstructed | /03L-0:on 810203 & 19,unit 1 Cable Spread Room Sprinkler Sys Was Inoperable for Period Greater than 14 Days & Special Repts Were Not Issued.Caused by Personnel Error. Personnel Reinstructed | | | 05000366/LER-1981-007-03, /03L-0:on 810126,discovered That on 810124 & 25 Reactor Coolant Sampled from Wrong Sample Line.Caused by Lack of Communication Among Personnel Who Collect & Analyze Reactor Coolant.Personnel Instructed & Coolant Sampled | /03L-0:on 810126,discovered That on 810124 & 25 Reactor Coolant Sampled from Wrong Sample Line.Caused by Lack of Communication Among Personnel Who Collect & Analyze Reactor Coolant.Personnel Instructed & Coolant Sampled | | | 05000366/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000321/LER-1981-008-03, /03L-0:on 810216,in Normal Operations at 309 Mwt, 1E51-N012A,B,C & D Actuated at 10.2,11.3,11.2 & 10.7 Psig, Respectively.Caused by Switch Setpoint Drift.Barksdale Switches Recalibr | /03L-0:on 810216,in Normal Operations at 309 Mwt, 1E51-N012A,B,C & D Actuated at 10.2,11.3,11.2 & 10.7 Psig, Respectively.Caused by Switch Setpoint Drift.Barksdale Switches Recalibr | | | 05000321/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000366/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000366/LER-1981-008-03, /03L-0:on 810119,pressure Switches Were Found Out of Tolerance.Caused by Setpoint Drift.Pressure Switches Recalibr & Returned to Svc | /03L-0:on 810119,pressure Switches Were Found Out of Tolerance.Caused by Setpoint Drift.Pressure Switches Recalibr & Returned to Svc | | | 05000366/LER-1981-009-03, /03L-0:on 810212,reactor Coolant Not Analyzed Once Per 24-h as Required by Tech Spec.Caused by Reactor Vessel Hydro During Time Period When Next Conductivity Measurement Was to Be Taken | /03L-0:on 810212,reactor Coolant Not Analyzed Once Per 24-h as Required by Tech Spec.Caused by Reactor Vessel Hydro During Time Period When Next Conductivity Measurement Was to Be Taken | | | 05000366/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | | | 05000321/LER-1981-009-03, /03L-0:on 810206,nitrogen Storage Tank Inventory Went Below 2000 Gallon Tech Spec Requirement.Caused by Supplier Delaying Shipment.Shipment Received.Supplier Instructed Not to Delay Shipments | /03L-0:on 810206,nitrogen Storage Tank Inventory Went Below 2000 Gallon Tech Spec Requirement.Caused by Supplier Delaying Shipment.Shipment Received.Supplier Instructed Not to Delay Shipments | | | 05000321/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | | | 05000366/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000366/LER-1981-010-03, /03L-0:on 810222,reactor Core Isolation Cooling Auto Flow Controller Did Not Control Turbine Properly While in Auto Position During Quickstart Test.Caused by Loose Ribbon Connector on Flow Control M-4 Station | /03L-0:on 810222,reactor Core Isolation Cooling Auto Flow Controller Did Not Control Turbine Properly While in Auto Position During Quickstart Test.Caused by Loose Ribbon Connector on Flow Control M-4 Station | | | 05000321/LER-1981-010, Forwards LER 81-010/01T-0 | Forwards LER 81-010/01T-0 | | | 05000321/LER-1981-010-01, /01T-0:on 810211,AE Reported That Diesel Generator 1A,1C,2A,2B & 1B Outlet Svc Water Piping & Associated Seismic Supports Exceeded Tech Spec.Caused by Design Omission.Design Mods Made | /01T-0:on 810211,AE Reported That Diesel Generator 1A,1C,2A,2B & 1B Outlet Svc Water Piping & Associated Seismic Supports Exceeded Tech Spec.Caused by Design Omission.Design Mods Made | | | 05000321/LER-1981-011-03, /03L-0:on 810214,liquid Radwaste Sample Tank, WSTB1,discharged Prior to Analysis,Contrary to Ets.Caused by Technician Error in Collecting Unit 2 Radwaste Sample in Prelabeled Unit 1 WSTB-1 Bottle | /03L-0:on 810214,liquid Radwaste Sample Tank, WSTB1,discharged Prior to Analysis,Contrary to Ets.Caused by Technician Error in Collecting Unit 2 Radwaste Sample in Prelabeled Unit 1 WSTB-1 Bottle | | | 05000321/LER-1981-011, Forwards LER 81-011/03L-0 | Forwards LER 81-011/03L-0 | | | 05000366/LER-1981-011-03, /03L-0:on 810204,nonrated Window Discovered in 3-h Rated Fire Wall.Caused by Design,Mfg & Const/Installation Error.Direct Conversion Reactor Study 81-48 Submitted & Fire Watch Established | /03L-0:on 810204,nonrated Window Discovered in 3-h Rated Fire Wall.Caused by Design,Mfg & Const/Installation Error.Direct Conversion Reactor Study 81-48 Submitted & Fire Watch Established | | | 05000366/LER-1981-011, Forwards LER 81-011/03L-0 | Forwards LER 81-011/03L-0 | | | 05000321/LER-1981-012-03, /03L-0:on 810228,turbine Failed to Trip on Overspeed.Caused by Dried Lubrication Around Overspeed Tripping Mechanisms Causing Binding.Mechanism Disassembled, Cleaned,Relubricated & Reassembled | /03L-0:on 810228,turbine Failed to Trip on Overspeed.Caused by Dried Lubrication Around Overspeed Tripping Mechanisms Causing Binding.Mechanism Disassembled, Cleaned,Relubricated & Reassembled | | | 05000321/LER-1981-012, Forwards LER 81-012/03L-0 | Forwards LER 81-012/03L-0 | | | 05000366/LER-1981-012-02, /02L-0:on 810224,during Surveillance Testing, Standby Liquid Control Pump B Failed to Start,Losing Squibb Valve B Continuity.Caused by Failure of Control Fuse in Circuit Breaker.Fuse Replaced | /02L-0:on 810224,during Surveillance Testing, Standby Liquid Control Pump B Failed to Start,Losing Squibb Valve B Continuity.Caused by Failure of Control Fuse in Circuit Breaker.Fuse Replaced | | | 05000366/LER-1981-012, Forwards LER 81-012/02L-0 | Forwards LER 81-012/02L-0 | | | 05000366/LER-1981-013, Forwards LER 81-013/03L-0 | Forwards LER 81-013/03L-0 | | | 05000321/LER-1981-013-03, /03L-0:on 810228,HPCI Sys Was Declared Inoperable When Oil Line Near Rear Bearing Broke.Caused by Person Stepping on Oil Line & Turbine Vibration Finishing Separation.Line Repaired | /03L-0:on 810228,HPCI Sys Was Declared Inoperable When Oil Line Near Rear Bearing Broke.Caused by Person Stepping on Oil Line & Turbine Vibration Finishing Separation.Line Repaired | |
|